IR 05000327/1980018
| ML19320B278 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/27/1980 |
| From: | Herdt A, Modenos L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19320B275 | List: |
| References | |
| 50-327-80-18, IEB-79-14, NUDOCS 8007100131 | |
| Download: ML19320B278 (3) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION g
a REGION 11
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o 101 MARIETTA ST., N.W.. SUITE 3100 Y4 o
ATLANTA, GEORGIA 30303
liAY 2 81880 Report No. 50-327/80-18 Licensee: Tennessee Valley Authority 500A Chestnut Street Chattanooga, TN 37401 Facility Name: Sequoyah Nuclear Plant Docket No. 50-327 License No. CPPR-72 Inspection at Sequoyah a r S ddy Daisy, Tennessee Inspector:
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Approved by:
[J A. R. Herdt, Section Chief, RCES Branch Date Signed SUMMARY Inspection on May 12-13, 1980
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Areas Inspected This special, announced inspection involved 12 inspector-hours on site in the area of seismic analysis for as-built safety-related piping systems (IE Bulletin 79-14).
Results No items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- J. M. Ballentine, Plant Superintendent
- C. R. Brimer, Outtge Director
- R. Guthrie, Civil Engineer Supervisor
- J. Beason, Civil Engineer Other licensee employees contacted included construction craftsmen, and QC inspectors.
NRC Resident Inspector
- S. D. Butler
- Attended exit interview 2.
Exit Interview The inspection scop
_adings were summarized on May 13, 1980 with those persons indica..
in Paragraph I above.
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Licensee Action on Previous Inspection Findings Not inspected.
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Unresolved Items Unresolved items were not identified during this inspection.
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(0 pen) Seismic Analysis for As-Built Safety-Related Piping Systems (IE Bulletin 79-14)
A Confirmation of Action Letter (CAL) was issued by the NRC on April 29, 1980 so as to provide additional assurance to Region II on the licensee satisfying the requirements for IE Bulletin 79-14.
The licensee selected as a representative sample, for items 2 and 3 of CAL, one isometric from eight safety-related systems plus ten supports from each of the remaining four safety-related systems inside containment. Approximately 265 supports were identified under this sample with field inspection completed on 223 supports.
Of the 223 inspected only 50 were under final review by the Engineering Design (EN DES) droup and 24 were identified to have some small
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discrepancies. All the discrepancies with the exception of two supports l
were accepted by EN DES as is, since there was no effect on the operability j
of the supports. The two supports identified to have a problem were SIS-1-
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H20-86 and SIS-1-H20-315. Su1> port No. 86 was designed to have a horizontal restraint while support No. 315 was designed for both a vertical and a m.
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-2-horizontal restraint. The inspector found the restraints on these supports adjacent to each other to be reversed, support No. 86 had both vertical and horizontal restraints and support No. 315 had a horizontal support caly.
The inspector reinspected these two supports and verified their findings but also questioned the EN DES personnel on checking further the edjacent supports to support No. 315 and its isometric.
It was not clear to the inspector the function of the support as called out by the design drawings and the actual supports found in the field. The inspector informed the management when a discrepancy is found as above further inspections sur-rounding the area in goestion would be required. The licensee concurred with this item.
The inspector reviewed all the final reviewed supports and the respective isometrics confirming indepth detail inspections that had been performed on these supports. The inspector witnessed inspection on the RHR package No.
39 and CVC package 52 systems that had been conducted by the QC inspection teams outside the containment in the Auxiliary Building. The inspector
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reviewed procedure MI-6.17 " Instructions for the Implementation of NRC IE Bulletin 79-14" which was used as the guide to the above inspections.
This IE Bulletin 79-14 remains open until all inspections and evaluations are completed and evaluated by the NRC.
No items of noncompliance or deviations were identified.
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